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This document provides the loading and operating conditions for eight 16-inch or five 24-inch elements, either natural NIN-1 or .947% enriched NIE-1, in any of the four KER loops. The loadings are tabulated; operating conditions for either charge in KER 2, 3, 4, or 1 are given in figures.

The purpose of this report is to establish the scope of a project to provide a system which will quickly and accurately identify the sources of all reactor scrams.

Three fuel element assemblies, each containing U-Mo fuel plates, will be irradiated in a side test hole at KE-Reactor. This document presents efforts made to determine the heat generation rate of the fuel plates from data from a capsule mockup irradiation in HTR.

This report is the second in a series on the definition of performance of irradiated fuel elements as measured by the Quality Certification Program. Objectives of this analysis are to establish empirical mathematical relations which fit observed data from > 2000 fuel elements measurements for WARP, TFC, and DELTA OD{sub 2}, as a function of reactor conditions (power, surface temperature, time).

The graphite stacks of the K reactors have been distorted to the extent that steel balls from the ball 3X system have entered some of the horizontal control rod channels and have interferred with the proper operation of the control system. One possible method of eliminating this potential hazard and attendant recurring production loss would be to place stationary sleeves around the horizontal control rods. Liners or sleeves in the vertical-ball and rod channels would prevent future leakage of balls into the moderator but would not eliminate the potential for balls already in the moderator to enter the horizontal control rod channels. For either horizontal or vertical liners it would be desirable to use an uncooled material which could withstand the reactor environment and which would not adversely affect the operation and production capacity of the reactor. The nuclear properties of five different materials have been reviewed to determine the maximum temperature which might be attained by each material when used as an uncooled sleeve, the effect each would have on the reactivity of the reactor, and the effect of each on the control capacity of the horizontal rod system. The five materials considered were: Inconel, a 300 series stainless …

Variables affecting the texture and grain size of uranium during beta treatment are summarized. The study of the effect of time and temperature in the beta phase on the growth index (G3) and grain size of the final alpha product is tentatively believed to show that higher beta temperatures for short times (up to about seven minutes) tend to promote slightly more negative growth indices and that higher beta temperatures give rise to somewhat finer grain sizes. Results of studies of both Jominy end-quenched bars and several full-sized rods and tubes quenched by total immersion showed that large thermal gradients promoted negative growth indices and produced grains somewhat elongated in the direction of the thermal gradient. The effects of endcooling in full-sized pieces quenched by total immersion in cold water showed that the axial growth index is negative up to distances from the end of about half the wall thickness of tubes and about half the radial dimension of rods. The grain refinement penetrates to a lesser distance from the ends. In the radial direction the growth index for these same pieces is largely negative to a distance below the outer diameter of about midwall in two tubes studied. In …

The thermal and total epithermal neutron flux distributions in the EGCR from the center of the core through the biological shield were calculated. The maximum values of the flux distribution are presented in graph form. Ordinary concrete was found to permit a thermal flux buildup, similar to that found in the graphite reflector. In heavy concrete there was no such buildup seen, since the thermal flux is attenuated through the complete shield. A Val Prod code using multigroup diffusion theory was used to calculate the neutron flux distributions. Calculations are shown. (M.C.G.)

As part of the coolant-core evaluation studies in an early phase of the Maritime Gas-Cooled Reactor program, nickel. K-Monel, niobium-1 wt.% zirconium, and graphite were irradiated in a convective flow of helium. A capsule of novel design was used to study the corrosion of the metals at 1500 and 960 ction prod- F in a 243-hr BRR experiment. Four heliumfilled quartz tori, containing the specimens, were encapsulated in a stainless steel capsule. A convective flow of helium was maintained in the closed tori by heating one leg of each torus to 1500 and the other at 960-F. Zirconium foilwas placed in two of the tori to getter gaseous impurities. No attack of the nickel and niobium-1 wt.% zirconium was observed at either temperature. Metallographic examination did show a 1 to 2.5- mil attack of the K-Monel at 1500 ction prod- F in a torus containing no getter. (auth)

A nontechnical description of the mechanisms of local and world-wide fall-out from nuclear explosions is given. The relative importance of local fall-out in a nuclear war is discussed. The effects upon man of world-wide fall-out from past nuclear testing is discussed. It is pointed out that doses to man frcm testing are quite small when compared to the natural radiation background. (auth)

BS>Ruthenium, either as soluble salts, powdered metal, or oxide, catalyzed the oxidation of Cr(III) to Cr(VI) in dilute oxygenated sulfuric acid solutions. Under the same conditions, in the absence of ruthenium, Cr(Vl) was not produced. In a 2 M Al(NO/sub 3/)/sub 3/-1 M HNO/sub 3/ solution at atmospheric boiling point, ruthenium and compounds of ruthenium, platinum, palladium, rhodium, and osmium very markedly increased the rate at which Cr(III) was oxidized to Cr(VI). Very low concentrations of ruthenium were capable of causing the oxidation to proceed at an appreciable rate. In boiling 65% nitric acid, Cr(HI) was oxidized to Cr(VI) if reduced oxides of nitrogen were removed from solution either m the presence or absence of ruthenium; without removal of the oxides of nitrogen, detectable quantities of Cr(VI) were not formed in either case. Cr(VI) was not produced in boiling and aerated uranyl sulfate solutions containing ruthenium. (auth)

Fission prcduct cross sections were measured radiochemically and mass- spectrometrically for gold bombsrded with 112-Mev C/sup 12/ ions. Cross sections for 43 nuclides were measured for elements from nickel to barium. Thirty-six yields are either primary fission product yields (independent yields) or were corrected (with less than 25% correction) so as to represent independent yields. The independent yields were empirically systematized and a yield-mass curve was constructed. The yield-mass curve is compared with the yield-mass curves obtained from the fission of Bi with 22 and 190-Mev deuterons. The yield systematics indicate that the sum of the mass numbers of complementary fission products is 13 plus or minus 1 amu less tban that of the compound nucleus, and the sum of the charges of complemertary fission products is two units less than that of the compound nucleus. It is postulated that 9 plus or minus 1 neutrons and an alpha particle must have been emitted. Evidence is presented that at least three and possibly more of the neutrons are emitted prior to fission. The most probable charge of the fission products as a function of mass number was determined empirically. It is shown that from mass number 80 to mass number …

Experiments were carried out on a Cs/sup 137/ plaque source of 40 x 40 x 1/2 inches. Measurements were made of dose distributions in water and of photon spectral distributions in paraffin. For 9-inch-thick water siab absorbers without air gaps, it was found from the preliminary experiments that the depth dose uniformity can be varied over the range 1.10 to 1.40. The absolute dose rates found were in general agreement with design predictions which indicate irradiator efficiencies in the region of 50% and dose rates in the region of 1 Megarad/hour for high-level indicators. (W.D.M.)

Tests were conducted to determine the cumulative and permanent deflection of a beam subjected to two-point loading for (1) ambient temperature- atmospheric environment, and (2) 800 deg F-atmospheric environment, for 8OO psi maximum flexural stresses. Deflection curves are given for five specimens. An analysis of the data indicated that if the core graphite creeps while at EGCR conditions by approximately 1.5 times its creep rate at ambient temperature, the stresses will level off below 1000 psi. Considerable oxidation oc curred for two specimens at 800 deg F. The indicated strain of these specimens may not be representative of AGOT, nuclear grade graphite at 800 deg F in an inert atmosphere. (B.O.G.)

An attempt is made to provide a single reference source for material pertinent to the maintenance and operation of the AE-6 Reactor. Descriptions of various components are included, as well as the common operational and maintenance procedures and check lists. Information is given on the subcritical assemblies that may be studied. (W.D.M.)

The criteria and methods for test evaluation of electromagnetic clutch characteristics are discussed. An evaluation of the relative merits of two commercial clutches, both of the multiple disk friction type, is presented with test results. One of these clutches was incorporated in the clutch assembly design for the Array Reactor (SM-2). (auth)